GB968763A - Improvements in the storage treatment of radioactive solutions containing molybdenum - Google Patents
Improvements in the storage treatment of radioactive solutions containing molybdenumInfo
- Publication number
- GB968763A GB968763A GB3471362A GB3471362A GB968763A GB 968763 A GB968763 A GB 968763A GB 3471362 A GB3471362 A GB 3471362A GB 3471362 A GB3471362 A GB 3471362A GB 968763 A GB968763 A GB 968763A
- Authority
- GB
- United Kingdom
- Prior art keywords
- glass
- solution
- temperature
- evaporated
- containing molybdenum
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
- G21F9/305—Glass or glass like matrix
Landscapes
- Chemical & Material Sciences (AREA)
- Inorganic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Glass Compositions (AREA)
Abstract
A solution containing molybdenum and radio-active fission products is evaporated and the residue incorporated into a phosphate glass which contains at least 35% by weight of free or combined phosphorus pentoxide. The glass may also include one or more oxides or mineral salts of lead, iron, aluminium, zinc, chromium, calcium, barium, and strontium. The solution is evaporated, the residue preferably pulverized, and the powder calcined to oxides before formation of the final glass, which may be formed by mixing the calcined powder with the components of the glass or with a frit of the glass. Alternatively the radio-active solution may be mixed with a solution of the glass components in phosphoric acid and the whole evaporated to give a residual glass. The constituents are preferably heated at a temperature about 20 DEG C. above the fusion temperature of the phosphate glass, i.e. a temperature in the range 600 DEG to 1200 DEG C. and preferably a temperature below 1050 DEG C.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR872930A FR1307309A (en) | 1961-09-12 | 1961-09-12 | Treatment of waste solutions of irradiated nuclear fuels of the uranium-molybdenum type |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB968763A true GB968763A (en) | 1964-09-02 |
Family
ID=8762658
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB3471362A Expired GB968763A (en) | 1961-09-12 | 1962-09-11 | Improvements in the storage treatment of radioactive solutions containing molybdenum |
Country Status (2)
| Country | Link |
|---|---|
| FR (1) | FR1307309A (en) |
| GB (1) | GB968763A (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3966852A (en) * | 1971-10-28 | 1976-06-29 | Siemens Aktiengesellschaft | Method for preparing test specimens for analysis |
| US4139488A (en) * | 1975-06-26 | 1979-02-13 | Vereinigte Edelstahlwerke Aktiengesellschaft | Method of preparing solid radioactive or toxic waste for long-term storage |
| US4344872A (en) | 1978-07-17 | 1982-08-17 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Method and apparatus for removing waste products from solutions of fission products |
| GB2130428A (en) * | 1982-10-21 | 1984-05-31 | Nukem Gmbh | A process for reducing the volume of aqueous radioactive waste |
| GB2130783A (en) * | 1982-10-21 | 1984-06-06 | Nukem Gmbh | A process for the solidification of aqueous radioactive waste |
| FR2562887A1 (en) * | 1984-04-11 | 1985-10-18 | Us Energy | LEAD AND IRON PHOSPHATE GLASS AS A CONTAINMENT MEDIUM FOR THE EVACUATION OF HIGHLY ACTIVE NUCLEAR WASTE |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4424149A (en) * | 1980-06-20 | 1984-01-03 | Kraftwerk Union Aktiengesellschaft | Method for ultimate disposition of borate containing radioactive wastes by vitrification |
| JPS6036999A (en) * | 1983-08-09 | 1985-02-26 | 株式会社荏原製作所 | Volume-reduction solidified body of radioactive sodium borate waste liquor, volume-reduction solidifying method anddevice thereof |
-
1961
- 1961-09-12 FR FR872930A patent/FR1307309A/en not_active Expired
-
1962
- 1962-09-11 GB GB3471362A patent/GB968763A/en not_active Expired
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3966852A (en) * | 1971-10-28 | 1976-06-29 | Siemens Aktiengesellschaft | Method for preparing test specimens for analysis |
| US4139488A (en) * | 1975-06-26 | 1979-02-13 | Vereinigte Edelstahlwerke Aktiengesellschaft | Method of preparing solid radioactive or toxic waste for long-term storage |
| US4344872A (en) | 1978-07-17 | 1982-08-17 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Method and apparatus for removing waste products from solutions of fission products |
| GB2130428A (en) * | 1982-10-21 | 1984-05-31 | Nukem Gmbh | A process for reducing the volume of aqueous radioactive waste |
| GB2130783A (en) * | 1982-10-21 | 1984-06-06 | Nukem Gmbh | A process for the solidification of aqueous radioactive waste |
| FR2562887A1 (en) * | 1984-04-11 | 1985-10-18 | Us Energy | LEAD AND IRON PHOSPHATE GLASS AS A CONTAINMENT MEDIUM FOR THE EVACUATION OF HIGHLY ACTIVE NUCLEAR WASTE |
Also Published As
| Publication number | Publication date |
|---|---|
| FR1307309A (en) | 1962-10-26 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| GB1087388A (en) | Isocyanate containing compositions and processes for their preparation | |
| GB968763A (en) | Improvements in the storage treatment of radioactive solutions containing molybdenum | |
| GB1021932A (en) | Improvements in and relating to polyphosphate glass | |
| GB1009694A (en) | Hydrogen source | |
| GB818963A (en) | Polyethylene of improved stability | |
| GB406142A (en) | Improvements in glass which resists attack by metal vapours | |
| ES486159A1 (en) | Metallic chromate pigment compositions and process for preparing them. | |
| GB1048313A (en) | Composition for treating water | |
| US3265627A (en) | Addition of lithium values in conversion of fission-product wastes to a glass-like solid for disposal | |
| GB896660A (en) | Improvements in the preparation of phosphates of bivalent metals | |
| GB1227166A (en) | ||
| GB1076335A (en) | Radioactive ceramic source and method of manufacture | |
| GB1078317A (en) | Polyurethane materials | |
| Hepworth et al. | 119. Complex fluorides of quadrivalent osmium and iridium and the corresponding free acids | |
| GB816412A (en) | Improved silica glass and process for its manufacture | |
| GB825976A (en) | Production of phosphates | |
| GB1433419A (en) | Method of treating phosphoric acid esters for storage in a non- polluting manner | |
| GB807570A (en) | Improvements in or relating to scintillators | |
| JPS5641290A (en) | Production of self-luminous paint | |
| GB1492464A (en) | Process for calcining radioactive wastes containing sodium nitrate | |
| GB785626A (en) | Improvements in or relating to the treatment of water | |
| GB1013897A (en) | Hydrates of fluoro-ketones and their preparation | |
| GB953963A (en) | Method of preparing strontium titanate | |
| ES401503A1 (en) | Method of producing a citrate-soluble calcined alkali metal phosphate fertiliser | |
| GB1182085A (en) | Method of Preparing Boric Oxide |